Manufacturing of ODS RAFM Steel: Mechanical and Microstructural Characterization

Abstract:

Ferritic ODS 14Cr steels reinforced by means of Yttrium oxide nanoclusters represent one of the options for future structural applications in nuclear Generation IV reactors. Due to their high tensile properties and resistance to irradiation damage, Oxide Dispersion Strengthened Steels (ODS-S) have been suggested for nuclear fusion applications. The present paper describes the experimental procedure of mechanical alloying, canning and hot extrusion adopted to produce ODS rods. The effect of variations in the processing parameters are also discussed. Hot extrusion has been successfully applied to produce a batch of about 10 kg of ODS steel. Full size ASTM E21 and E8 specimens have been tested from room temperature up to 800 °C. The microstructure characterization of the manufactured materials has been carried out by transmission electron microscopy. Ultimate tensile stress higher than 1350 MPa have been obtained in the as-extruded material and higher than 1100 MPa in samples annealed for 4 hours at 800 °C.

• Periodical: Materials Science Forum (Volume 879)
• Pages: 1639-1644
• DOI: https://doi.org/10.4028/www.scientific.net/MSF.879.1639
• Online since: November 2016
• Authors: Claudio Testani, Paolo Emilio di Nunzio*, Ilaria Salvatori
• Keywords: Hot Extrusion, Mechanical Alloying, Mechanical Testing, Microstructure, Nanoprecipitation, ODS Steel

References

[1] S. Ukai et al., J. Nucl. Mater., 204 (1993) 65-73.

[2] S. Ukai, M. Fujiwara, J. Nucl. Mater., 307–311 (2002) 749-57.

[3] R.L. Klueh et al., J. Nucl. Mater., 307-311 (2002) 455-65.

[4] P. Unifantowicz et al., Proc. of the 24th IAEA Fusion Energy Conference, (2012).

[5] V. de Castro et al., J. Nucl. Mater., 417 (2011) 217-220.

[6] V. de Castro et al., J. Nucl. Mater., 367-370 (2007) 196-201.

[7] M. Yurechko et al., J. Nucl. Mater., 450 (2014) 88-98.

[8] J.S. Veternikova et al., J. of Nucl. Mater., 450 (2014) 99-103.

[9] H.S. Cho, A. Kimura, S. Ukai, M. Fujiwara, J. Nucl. Mater., 329–333 (2004) 387-391.

[10] A. Ramar, N. Baluc, R. Schäublin, J. of Nucl. Mater., 386-388 (2009) 515-519.

[11] Y. De Carlan et al., J. Nucl. Mater., 386-388 (2009) 430-32.

[12] M. Wang, Z. Zhou, H. Sun, H. Hu, S. Li, Mater. Sci. Eng., A, 559 (2013) 287-92.

[13] M. Kawahara, H. Kim, M. Tokita, Proc. of Powder Metallurgy World Congress, 741; (2000).

[14] H. W. Zhang, R. Gopalan, T. Mukai, K. Hono, Scripta Mater., 53 (2005) 863-873.

[15] M. Cabibbo et al., Mater. Sci. Forum, 604-605 (2009) 203-211.

[16] G. Ji, T. Grosdidier, N. Bozzolo, S. Launois, Intermetallics, 15 (2007) 108-118.

[17] X. Boulnat et al., Metall. and Mater. Trans. A, 44A (2013) 2461-2464.

[18] Z. S. Chen et al., Bull. Mater. Sci., Vol. 34 (2011), 429–434.

[19] S. Ukai, Mater. Sci. Eng. A 510–511 (2009) 115–120.

[20] Z. Lu et al., Acta Metall. Sin. 48 (2012) 62-85.

[21] http: /www. matcalc. tuwien. ac. at.

[22] Bhaskar S. Majumdar, Mater. Sci. Eng. A , 259 (1999) 171–188.

[23] A. Alamo et al., J. Nucl. Materials 329–333 (2004) 333–337.